2020•Annals of Nuclear EnergyRequires access

Research and development of a transient thermal–hydraulic code for system safety analysis of sodium cooled fast reactor

Yang Yu, Dong Liu, Xiaoming Song, Zhongchun Li, Fengchen Guo, Yafeng Wang, Bo Pang

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Key concepts: Sodium-cooled fast reactor, Thermal hydraulics, Transient (computer programming), Nuclear engineering, Coolant, Decay heat, Heat transfer, Environmental science

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Research and development of a transient thermal–hydraulic code for system safety analysis of sodium cooled fast reactor — Research Paper | ScholarLens